According to a first aspect, there is provided a nuclear fission reactor. The nuclear fission reactor comprises a core, a tank surrounding the core, and a cooling system located outside the tank. The cooling system comprises one or more structures configured to absorb thermal radiation emitted from an outer wall of the tank. The structures are not substantially thermally coupled to the tank except by radiation. The cooling system further comprises a cold air inlet and a hot air outlet, positioned such that air flows from the cold air inlet to the hot air outlet over, around and/or through the one or more structures.

A nuclear reactor includes a pressure vessel and a nuclear reactor core comprising fissile material disposed inside the pressure vessel at the bottom of the pressure vessel. A secondary core containment structure includes a containment basket comprising insulation with a maximum stable temperature of at least 2200K cladded by steel. The bottom of the pressure vessel and the nuclear reactor core are disposed inside the containment basket with the containment basket spaced apart from the bottom of the pressure vessel by a clearance gap. The containment basket may comprise zirconia insulation cladded by steel. In some embodiments the clearance gap between the containment basket and the bottom of the pressure vessel is no larger than one meter. The secondary core containment structure may further comprise conduits arranged to inject water into the clearance gap between the containment basket and the bottom of the pressure vessel.

An annular nuclear fuel pellet in combination with an inserted discrete neutron absorber. The pellet/absorber may be compatible with existing or future nuclear fuel assembly designs. The concept involves the use of nuclear fuel (e.g., uranium dioxide or uranium silicide) formed into annular fuel pellets which can then have a discrete absorber material inserted into the center of the pin. Preferably, the discrete absorber is a non-parasitic absorber. The resulting pellet/absorber can then be stacked into a fuel rod which is arranged in a nuclear fuel assembly. Dimensioning of the annular pellet and absorber and selection of the absorber material and density can allow the concept to be tailored for various nuclear fuel applications.

A Modular Isolated Reactor Support System (MIRSS) assembly includes a cylindrical reactor support structure configured to structurally support a reactor enclosure system on seismic isolators, a collector cylinder configured to at least partially define a riser annulus between an inner cylindrical surface of the collector cylinder and an outer sidewall surface of the reactor enclosure system structurally supported by the cylindrical reactor support structure, and a divider wall configured to at least partially define a downcomer annulus between an outer cylindrical surface of the divider wall and a reactor building, and a plurality of exhaust ducts extending from the collector cylinder and through an interior of the cylindrical reactor support structure.

Systems and methods for insulating vessels are disclosed. In one or more embodiments, the disclosure provides a vessel insulation system (e.g., for use with a reactor or pressure vessel), which includes a floating ring sized to circumscribe a top nozzle of a vessel; a plurality of straps connected to the floating ring, the plurality of straps extending downward from the floating ring and being positioned to run along a length of the outer shell of the vessel; and a plurality of segmented rings positioned to circumscribe the outer shell of the vessel and connected to the plurality of straps. The plurality of segmented rings is configured to support an insulation material circumscribing the outer shell of the vessel, which can provide effective securement of the insulation material around the outer shell without welding components on the vessel to secure the insulation material.

A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from within the containment vessel.

A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from within the containment vessel.

This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor for managing the operating temperature in the reactor core. The disclosure includes various configurations of direct reactor auxiliary cooling system (DRACS) heat exchangers and primary heat exchangers as well as descriptions of improved flow paths for nuclear fuel, primary coolant and DRACS coolant through the reactor components.

This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor in which one or more primary heat exchangers are located above the reactor core of the nuclear reactor.

This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor in which one or more primary heat exchangers are located above the reactor core of the nuclear reactor.